Journal Publications of the Severe Accident Research Group

Our scientists, post docs and students regularly publish articles in scientific magazines primarily in the nuclear engineering and technical field. For this purpose, each submitted article is first thoroughly reviewed and then approved.

Here you will find a selection of journals that regularly publish articles from our laboratory:

2025

Lind T, Espegren F, Suckow D
An experimental study of iodine retention in Ag-zeolites at high humidity conditions
Frontiers in Nuclear Engineering. 2025; 4: 1567507 (11 pp.). https://doi.org/10.3389/fnuen.2025.1567507
DORA PSI

2024

Malicki M, Darnowski P, Lind T
An iPWR MELCOR 2.2 study on the impact of the modeling parameters on code performance and accident progression
Energies. 2024; 17(13): 3279 (24 pp.). https://doi.org/10.3390/en17133279
DORA PSI
Malicki M, Lind T
MELCOR 2.2 iPWR LOCA type accident analysis, PART I: Thermal-hydraulics
Nuclear Engineering and Design. 2024; 428: 113433 (13 pp.). https://doi.org/10.1016/j.nucengdes.2024.113433
DORA PSI
Mascari F, Bersano A, Massone M, Agnello G, Coindreau O, Beck S, et al.
Main outcomes of the Phebus FPT1 uncertainty and sensitivity analysis in the EU-MUSA project
Annals of Nuclear Energy. 2024; 196: 110205 (14 pp.). https://doi.org/10.1016/j.anucene.2023.110205
DORA PSI
Ramos Perez A, Lind T, Petrov V, Manera A, Prasser HM
Characterization of turbulent multiphase particle mass transfer in gas-liquid flows
International Journal of Heat and Mass Transfer. 2024; 234: 126044 (16 pp.). https://doi.org/10.1016/j.ijheatmasstransfer.2024.126044
DORA PSI
Ramos Perez A, Lind T, Petrov V, Manera A, Prasser HM
Two-phase hydrodynamics and aerosol mass transfer characterization in pool scrubbing: a simultaneous measurement technique
Journal of Aerosol Science. 2024; 178: 106336 (17 pp.). https://doi.org/10.1016/j.jaerosci.2024.106336
DORA PSI
Seyffert C, Malicki M
Validation methods in modelling the PANDA IPSS experiment: a MELCOR 2.2 assessment of a passive isolation condenser
Progress in Nuclear Energy. 2024; 177: 105430 (10 pp.). https://doi.org/10.1016/j.pnucene.2024.105430
DORA PSI

2023

Al-Yahia OS, Clifford I, Bissels W-M, Suckow D, Ferroukhi H
Experimental study for high Reynolds’ gas-liquid two-phase flow through rod bundle using Wire Mesh Sensor (WMS)
Nuclear Engineering and Design. 2023; 405: 112224 (23 pp.). https://doi.org/10.1016/j.nucengdes.2023.112224
DORA PSI
Coindreau O, Herranz LE, Bocanegra R, Ederli S, Maccari P, Mascari F, et al.
Uncertainty quantification for a severe accident sequence in a SFP in the frame of the H-2020 project MUSA: first outcomes
Annals of Nuclear Energy. 2023; 188: 109796 (9 pp.). https://doi.org/10.1016/j.anucene.2023.109796
DORA PSI
Gupta S, Herranz LE, Lebel LS, Sonnenkalb M, Pellegrini M, Marchetto C, et al.
Integration of pool scrubbing research to enhance Source-Term calculations (IPRESCA) project – overview and first results
Nuclear Engineering and Design. 2023; 404: 112189 (20 pp.). https://doi.org/10.1016/j.nucengdes.2023.112189
DORA PSI
Jäckel BS, Birchley JC, Lind T, Steinbrück M, Park S
Nitriding model for zirconium based fuel cladding in severe accident codes
Journal of Nuclear Materials. 2023; 582: 154466 (7 pp.). https://doi.org/10.1016/j.jnucmat.2023.154466
DORA PSI
Malicki M, Lind T
Impact of PSI-KIT nitriding model on hypothetical spent fuel pool accident simulation
Nuclear Engineering and Technology. 2023; 55(7): 2504-2515. https://doi.org/10.1016/j.net.2023.04.003
DORA PSI
Malicki M, Lind T
Parametric MELCOR 2.2 sensitivity and uncertainty study with a focus on aerosols based on Phébus test FPT1
Progress in Nuclear Energy. 2023; 158: 104609 (15 pp.). https://doi.org/10.1016/j.pnucene.2023.104609
DORA PSI
Mascari F, Bersano A, Adorni M, D'Ovidio G, Martín-Fuertes F, Jin XZ, et al.
Current status of MELCOR 2.2 for fusion safety analyses
Fusion Engineering and Design. 2023; 194: 113869 (7 pp.). https://doi.org/10.1016/j.fusengdes.2023.113869
DORA PSI

2022

Di Giuli M, Malicki M, Dejardin P, Corda V, Swaidan AM
MELCOR 2.2-ASTEC V2.2 crosswalk study reproducing SBLOCA and CSBO scenarios in a PWR1000-like reactor part I: analysis of RCS thermal-hydraulics and in-vessel phenomena
Nuclear Engineering and Design. 2022; 387: 111248 (22 pp.). https://doi.org/10.1016/j.nucengdes.2021.111248
DORA PSI
Janasz F, Prasser H-M, Suckow D, Mityakov A
The use of a novel gradient heat flux sensor for characterization of reflux condensation
Nuclear Engineering and Design. 2022; 395: 111885 (9 pp.). https://doi.org/10.1016/j.nucengdes.2022.111885
DORA PSI
Kalilainen J, Lind T
Uncertainty quantification study on gas phase iodine release from Fukushima Daiichi accident in unit 3
Annals of Nuclear Energy. 2022; 166: 108740 (13 pp.). https://doi.org/10.1016/j.anucene.2021.108740
DORA PSI
Nichenko S, Kalilainen J, Lind T
MSR simulation with cGEMS: fission product release and aerosol formation
Journal of Nuclear Engineering. 2022; 3(1): 105-116. https://doi.org/10.3390/jne3010006
DORA PSI

2021

Breitenmoser D, Papadopoulos P, Lind T, Prasser H-M
Droplet size distribution in a full-scale rectangular self-priming Venturi scrubber with liquid film injection
International Journal of Multiphase Flow. 2021; 142: 103694 (15 pp.). https://doi.org/10.1016/j.ijmultiphaseflow.2021.103694
DORA PSI
Choi YJ, Kam DH, Padopoulos P, Lind T, Jeong YH
Experimental investigation on bubble behaviors in a water pool using the venturi scrubbing nozzle
Nuclear Engineering and Technology. 2021; 53: 1756-1768. https://doi.org/10.1016/j.net.2020.11.024
DORA PSI
Lind T, Pellegrini M, Herranz LE, Sonnenkalb M, Nishi Y, Tamaki H, et al.
Overview and outcomes of the OECD/NEA benchmark study of the accident at the Fukushima Daiichi NPS (BSAF), Phase 2 – Results of severe accident analyses for unit 3
Nuclear Engineering and Design. 2021; 376: 111138 (12 pp.). https://doi.org/10.1016/j.nucengdes.2021.111138
DORA PSI
Nichenko S, Kalilainen J, Fernandez Moguel L, Lind T
Modelling of fission products release in VERDON-1 experiment with cGEMS: coupling of severe accident code MELCOR with GEMS thermodynamic modelling package
Annals of Nuclear Energy. 2021; 152: 107972 (11 pp.). https://doi.org/10.1016/j.anucene.2020.107972
DORA PSI
Skolik K, Allison C, Hohorst J, Malicki M, Perez-Ferragut M, Pieńkowski L, et al.
Analysis of loss of coolant accident without ECCS and DHRS in an integral pressurized water reactor using RELAP/SCDAPSIM
Progress in Nuclear Energy. 2021; 134: 103648 (15 pp.). https://doi.org/10.1016/j.pnucene.2021.103648
DORA PSI
Stuckert J, Steinbrueck M, Kalilainen J, Lind T, Birchley J
Experimental and modelling results of the QUENCH-18 bundle experiment on air ingress, cladding melting and aerosol release
Nuclear Engineering and Design. 2021; 379: 111267 (11 pp.). https://doi.org/10.1016/j.nucengdes.2021.111267
DORA PSI

2020

Betschart T, Lind T, Prasser H-M
Investigation of two-phase flow hydrodynamics under SGTR severe accident conditions
Nuclear Engineering and Design. 2020; 366: 110768 (14 pp.). https://doi.org/10.1016/j.nucengdes.2020.110768
DORA PSI
Herranz LE, Pellegrini M, Lind T, Sonnenkalb M, Godin-Jacqmin L, López C, et al.
Overview and outcomes of the OECD/NEA benchmark study of the accident at the Fukushima Daiichi NPS (BSAF) Phase 2 - results of severe accident analyses for Unit 1
Nuclear Engineering and Design. 2020; 369: 110849 (7 pp.). https://doi.org/10.1016/j.nucengdes.2020.110849
DORA PSI
Jäckel BS, Steiner P, Klügel J-U
Loss-of-cooling accident calculations for the wet storage pool of NPP Gösgen/Däniken
Nuclear Engineering and Design. 2020; 370: 110839 (6 pp.). https://doi.org/10.1016/j.nucengdes.2020.110839
DORA PSI
Kalilainen J, Nichenko S, Krepel J
Evaporation of materials from the molten salt reactor fuel under elevated temperatures
Journal of Nuclear Materials. 2020; 533: 152134 (13 pp.). https://doi.org/10.1016/j.jnucmat.2020.152134
DORA PSI
Lind T, Campbell S, Herranz LE, Kissane M, Song JH
A summary of fission-product-transport phenomena during SGTR severe accidents
Nuclear Engineering and Design. 2020; 363: 110635 (10 pp.). https://doi.org/10.1016/j.nucengdes.2020.110635
DORA PSI
Nakayoshi A, Rempe JL, Barrachin M, Bottomley D, Jacquemain D, Journeau C, et al.
Review of Fukushima Daiichi Nuclear Power Station debris endstate location in OECD/NEA preparatory study on analysis of fuel debris (PreADES) project
Nuclear Engineering and Design. 2020; 369: 110857 (15 pp.). https://doi.org/10.1016/j.nucengdes.2020.110857
DORA PSI
Pellegrini M, Herranz L, Sonnenkalb M, Lind T, Maruyama Y, Gauntt R, et al.
Main findings, remaining uncertainties and lessons learned from the OECD/NEA BSAF project
Nuclear Technology. 2020; 206(9): 1449-1463. https://doi.org/10.1080/00295450.2020.1724731
DORA PSI
Sonnenkalb M, Pellegrini M, Herranz LE, Lind T, Morreale AC, Kanda K, et al.
Overview and outcomes of the OECD/NEA benchmark study of the accident at the Fukushima Daiichi NPS (BSAF), phase 2 - results of severe accident analyses for unit 2
Nuclear Engineering and Design. 2020; 369: 110840 (10 pp.). https://doi.org/10.1016/j.nucengdes.2020.110840
DORA PSI
Vitullo F, Krepel J, Kalilainen J, Prasser H-M, Pautz A
Statistical burnup distribution of moving pebbles in the HTR-PM reactor
Journal of Nuclear Engineering and Radiation Science. 2020; 6(2): 021108 (14 pp.). https://doi.org/10.1115/1.4044910
DORA PSI

2019

Dehbi A, Kelm S, Kalilainen J, Mueller H
The influence of thermal radiation on the free convection inside enclosures
Nuclear Engineering and Design. 2019; 341: 176-185. https://doi.org/10.1016/j.nucengdes.2018.10.025
DORA PSI
Fernandez-Moguel L, Rydl A, Lind T
Updated analysis of Fukushima Unit 3 with MELCOR 2.1. Part 2: fission product release and transport analysis
Annals of Nuclear Energy. 2019; 130: 93-106. https://doi.org/10.1016/j.anucene.2019.02.017
DORA PSI
Fernandez-Moguel L, Rydl A, Lind T
Updated analysis of Fukushima unit 3 with MELCOR 2.1. Part 1: thermal-hydraulic analysis
Annals of Nuclear Energy. 2019; 123: 59-77. https://doi.org/10.1016/j.anucene.2018.09.008
DORA PSI
Kalilainen J, Lind T, Stuckert J, Bergfeldt T, Sippula O, Jokiniemi J
The measurement of Ag/In/Cd release under air-ingress conditions in the QUENCH-18 bundle test
Journal of Nuclear Materials. 2019; 517: 315-327. https://doi.org/10.1016/j.jnucmat.2019.02.021
DORA PSI
Lind T, Guentay S, Herranz LE, Suckow D
A summary of the ARTIST: aerosol retention during SGTR severe accident
Annals of Nuclear Energy. 2019; 131: 385-400. https://doi.org/10.1016/j.anucene.2019.04.006
DORA PSI
Rýdl A, Fernandez-Moguel L, Lind T
Modeling of aerosol fission product scrubbing in experiments and in integral severe accident scenarios
Nuclear Technology. 2019; 205(5): 655-670. https://doi.org/10.1080/00295450.2018.1511213
DORA PSI
Yang J, Suckow D, Lind T, Prasser H-M
Study of level swell for a Filtered Containment Venting System at the VEFITA facility
Progress in Nuclear Energy. 2019; 113: 7-17. https://doi.org/10.1016/j.pnucene.2019.01.003
DORA PSI

2018

Albiol T, Herranz L, Riera E, Dalibart C, Lind T, Del Corno A, et al.
Main results of the European PASSAM project on severe accident source term mitigation
Annals of Nuclear Energy. 2018; 116: 42-56. https://doi.org/10.1016/j.anucene.2018.02.024
DORA PSI
Beghi I, Lind T, Prasser H-M
Experimental studies on retention of iodine in a wet scrubber
Nuclear Engineering and Design. 2018; 326: 234-243. https://doi.org/10.1016/j.nucengdes.2017.11.025
DORA PSI
Coindreau O, Jäckel B, Rocchi F, Alcaro F, Angelova D, Bandini G, et al.
Severe accident code-to-code comparison for two accident scenarios in a spent fuel pool
Annals of Nuclear Energy. 2018; 120: 880-887. https://doi.org/10.1016/j.anucene.2018.06.043
DORA PSI
Gouëllo M, Kalilainen J, Kärkelä T, Auvinen A
Contribution to the understanding of iodine transport under primary circuit conditions: Csi/Cd and Csi/Ag interactions in condensed phase
Nuclear Materials and Energy. 2018; 17: 259-268. https://doi.org/10.1016/j.nme.2018.11.011
DORA PSI
Halouane Y, Dehbi A
CFD simulation of hydrogen mitigation by a passive autocatalytic recombiner
Nuclear Engineering and Design. 2018; 330: 488-496. https://doi.org/10.1016/j.nucengdes.2018.01.018
DORA PSI
Kim H, Dehbi A, Kalilainen J
Measurements and LES computations of a turbulent particle-laden flow inside a cubical differentially heated cavity
Atmospheric Environment. 2018; 186: 216-228. https://doi.org/10.1016/j.atmosenv.2018.05.037
DORA PSI
Marelli E, Villevieille C, Park S, Hérault N, Marino C
Co-Free P2–Na_0.67Mn_0.6Fe_0.25Al_0.15O₂ as promising cathode material for sodium-ion batteries
ACS Applied Energy Materials. 2018; 1(11): 5960-5967. https://doi.org/10.1021/acsaem.8b01015
DORA PSI

2017

Dehbi A, Kalilainen J, Lind T, Auvinen A
A large eddy simulation of turbulent particle-laden flow inside a cubical differentially heated cavity
Journal of Aerosol Science. 2017; 103: 67-82. https://doi.org/10.1016/j.jaerosci.2016.10.003
DORA PSI
Grimm P, Hursin M, Perret G, Siefman D, Ferroukhi H
Analysis of reactivity worths of burnt PWR fuel samples measured in LWR-PROTEUS Phase II using a CASMO-5 reflected-assembly model
Progress in Nuclear Energy. 2017; 101: 280-287. https://doi.org/10.1016/j.pnucene.2017.03.018
DORA PSI
Halouane Y, Dehbi A
CFD simulations of premixed hydrogen combustion using the Eddy Dissipation and the Turbulent Flame Closure models
International Journal of Hydrogen Energy. 2017; 42(34): 21990-22004. https://doi.org/10.1016/j.ijhydene.2017.07.075
DORA PSI
Karanki DR, Rahman S, Dang VN, Zerkak O
Epistemic and aleatory uncertainties in integrated deterministic and probabilistic safety assessment: tradeoff between accuracy and accident simulations
Reliability Engineering and System Safety. 2017; 162: 91-102. https://doi.org/10.1016/j.ress.2017.01.015
DORA PSI
Perret G, Geslot B, Gruel A, Blaise P, Di-Salvo J, De Izarra G, et al.
Kinetic parameter measurements in the Minerve reactor
IEEE Transactions on Nuclear Science. 2017; 64(1): 724-734. https://doi.org/10.1109/TNS.2016.2637569
DORA PSI

2016

Adorni M, Herranz LE, Hollands T, Ahn K-II, Bals C, D'Auria F, et al.
OECD/NEA Sandia Fuel Project phase I: benchmark of the ignition testing
Nuclear Engineering and Design. 2016; 307: 418-430. https://doi.org/10.1016/j.nucengdes.2016.07.016
DORA PSI
Beuzet E, Haurais F, Bals C, Coindreau O, Fernandez-Moguel L, Vasiliev A, et al.
Cladding oxidation during air ingress. Part II: synthesis of modelling results
Annals of Nuclear Energy. 2016; 93: 18-27. https://doi.org/10.1016/j.anucene.2015.12.031
DORA PSI
Bozzetti C, Daellenbach KR, Hueglin C, Fermo P, Sciare J, Kasper-Giebl A, et al.
Size-resolved identification, characterization, and quantification of primary biological organic aerosol at a European rural site
Environmental Science and Technology. 2016; 50(7): 3425-3434. https://doi.org/10.1021/acs.est.5b05960
DORA PSI
Daellenbach KR, Bozzetti C, Křepelová A, Canonaco F, Wolf R, Zotter P, et al.
Characterization and source apportionment of organic aerosol using offline aerosol mass spectrometry
Atmospheric Measurement Techniques. 2016; 9(1): 23-39. https://doi.org/10.5194/amt-9-23-2016
DORA PSI
Dehbi A
A unified correlation for steam condensation rates in the presence of air-helium mixtures under naturally driven flows
Nuclear Engineering and Design. 2016; 300: 601-609. https://doi.org/10.1016/j.nucengdes.2016.02.009
DORA PSI
Dehbi A, Suckow D, Lind T, Guentay S, Danner S, Mukin R
Key findings from the artist project on aerosol retention in a dry steam generator
Nuclear Engineering and Technology. 2016; 48(4): 870-880. https://doi.org/10.1016/j.net.2016.06.001
DORA PSI
Epiney A, Canepa S, Zerkak O, Ferroukhi H
Towards a consolidated approach for the assessment of evaluation models of nuclear power reactors
Nuclear Technology. 2016; 196(2): 223-237. https://doi.org/10.13182/NT16-47
DORA PSI
Jayaraju ST, Roelofs F, Komen EMJ, Dehbi A
RANS modeling of fluid flow and dust deposition in nuclear pebble-beds
Nuclear Engineering and Design. 2016; 308: 222-237. https://doi.org/10.1016/j.nucengdes.2016.08.037
DORA PSI
Jäckel BS, Bevilacqua A, Ducros G, Gauntt R, Stuckert J
Land contamination activity data interpretation from Fukushima Daiichi accident
Nuclear Engineering and Design. 2016; 300: 28-33. https://doi.org/10.1016/j.nucengdes.2015.12.030
DORA PSI
Kalilainen J, Rantanen P, Lind T, Auvinen A, Dehbi A
Experimental investigation of a turbulent particle-laden flow inside a cubical differentially heated cavity
Journal of Aerosol Science. 2016; 100: 73-87. https://doi.org/10.1016/j.jaerosci.2016.06.001
DORA PSI
Mignot G, Paranjape S, Paladino D, Jaeckel B, Rydl A
Large scale experiments simulating hydrogen distribution in a spent fuel pool building during a hypothetical fuel uncovery accident scenario
Nuclear Engineering and Technology. 2016; 48(4): 881-892. https://doi.org/10.1016/j.net.2016.06.005
DORA PSI
Mukin RV
Bubble reconstruction method for wire-mesh sensors measurements
Experiments in Fluids. 2016; 57(8): 133 (12 pp.). https://doi.org/10.1007/s00348-016-2220-y
DORA PSI
Mukin R, Dehbi A
Particle deposition modeling in the secondary side of a steam generator bundle model
Nuclear Engineering and Design. 2016; 299: 112-123. https://doi.org/10.1016/j.nucengdes.2015.09.001
DORA PSI
Pellegrini M, Dolganov K, Herranz LE, Bonneville H, Luxat D, Sonnenkalb M, et al.
Benchmark study of the accident at the Fukushima Daiichi NPS: best-estimate case comparison
Nuclear Technology. 2016; 196(2): 198-210. https://doi.org/10.13182/NT16-63
DORA PSI
Puragliesi R, Zhou L, Zerkak O, Pautz A
Steady-state CFD simulations of an EPR^TM reactor pressure vessel: a validation study based on the JULIETTE experiments
Nuclear Engineering and Design. 2016; 300: 41-56. https://doi.org/10.1016/j.nucengdes.2015.12.025
DORA PSI
Rabiti C, Alfonsi A, Epiney A
New simulation schemes and capabilities for the PHISICS/RELAP5-3D coupled suite
Nuclear Science and Engineering. 2016; 182(1): 104-118. https://doi.org/10.13182/NSE14-143
DORA PSI
Rýdl A, Lind T, Birchley J
Integral analyses of fission product retention at mitigated thermally-induced SGTR using ARTIST experimental data
Nuclear Engineering and Design. 2016; 297: 175-187. https://doi.org/10.1016/j.nucengdes.2015.11.014
DORA PSI
Wicaksono D, Zerkak O, Pautz A
Global sensitivity analysis of transient code output applied to a reflood experiment model using the TRACE code
Nuclear Science and Engineering. 2016; 184(3): 400-429. https://doi.org/10.13182/NSE16-37
DORA PSI

Bubbly, Slug, and Annular Two-Phase Flow in Tight-Lattice Subchannels
H.-M. Prasser, C. Bolesch, K. Cramer, D. Ito, P. Papadopoulos, A. Saxena, R. Zboray
Nuclear Engineering and Technology 48, 847
http://dx.doi.org/10.1016/j.net.2016.06.007

Liquid film dynamics of two-phase annular flow in square and tightlattice subchannels
D. Ito, P. Papadopoulos, H.-M. Prasser
Nuclear Engineering and Design 300, 467
http://dx.doi.org/10.1016/j.nucengdes.2016.02.034

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2015

Bosshard C, Deville MO, Dehbi A, Leriche E
UDNS or LES, that is the question
Open Journal of Fluid Dynamics. 2015; 5(4): 339-352. https://doi.org/10.4236/ojfd.2015.54034
DORA PSI
Dehbi A
A generalized correlation for steam condensation rates in the presence of air under turbulent free convection
International Journal of Heat and Mass Transfer. 2015; 86: 11754 (15 pp.). https://doi.org/10.1016/j.ijheatmasstransfer.2015.02.034
DORA PSI
Fernandez-Moguel L, Birchley J
Analysis of the accident in the Fukushima Daiichi nuclear power station unit 3 with MELCOR_2.1
Annals of Nuclear Energy. 2015; 83: 193-215. https://doi.org/10.1016/j.anucene.2015.04.021
DORA PSI
Fernandez-Moguel L
Comparative assessment of PSI air oxidation model implementation in SCDAPSim3.5, MELCOR 1.8.6 and MELCOR 2.1
Annals of Nuclear Energy. 2015; 81: 134-142. https://doi.org/10.1016/j.anucene.2015.03.015
DORA PSI
Fiorina C, Clifford I, Aufiero M, Mikityuk K
GeN-Foam: A novel OpenFOAM^® based multi-physics solver for 2D/3D transient analysis of nuclear reactors
Nuclear Engineering and Design. 2015; 294: 24-37. https://doi.org/10.1016/j.nucengdes.2015.05.035
DORA PSI
Freixa J, Martínez-Quiroga V, Zerkak O, Reventós F
Modelling guidelines for core exit temperature simulations with system codes
Nuclear Engineering and Design. 2015; 286: 116-129. https://doi.org/10.1016/j.nucengdes.2015.02.003
DORA PSI
Jayaraju ST, Sathiah P, Roelofs F, Dehbi A
RANS modeling for particle transport and deposition in turbulent duct flows: near wall model uncertainties
Nuclear Engineering and Design. 2015; 289: 60-72. https://doi.org/10.1016/j.nucengdes.2015.04.011
DORA PSI
Jäckel BS
Status of the spent fuel in the reactor buildings of Fukushima Daiichi 1-4
Nuclear Engineering and Design. 2015; 283: 2-7. https://doi.org/10.1016/j.nucengdes.2014.07.007
DORA PSI
Karanki DR, Kim T-W, Dang VN
A dynamic event tree informed approach to probabilistic accident sequence modeling: dynamics and variabilities in medium LOCA
Reliability Engineering and System Safety. 2015; 142: 78-91. https://doi.org/10.1016/j.ress.2015.04.011
DORA PSI
Yang J, Lim J, Choi SW, Lee DY, Rassame S, Hibiki T, et al.
Behaviors of passive safety systems under a feed water line break LOCA on a generation III + boiling water reactor
Progress in Nuclear Energy. 2015; 83: 35-42. https://doi.org/10.1016/j.pnucene.2015.02.011
DORA PSI
Zerkak O, Kozlowski T, Gajev I
Review of multi-physics temporal coupling methods for analysis of nuclear reactors
Annals of Nuclear Energy. 2015; 84: 225-233. https://doi.org/10.1016/j.anucene.2015.01.019
DORA PSI

2010-2014

Bosshard C, Dehbi A, Deville M, Leriche E, Soldati A
Large eddy simulation of particulate flow inside a differentially heated cavity
Nuclear Engineering and Design. 2014; 267: 154-163. https://doi.org/10.1016/j.nucengdes.2013.12.035
DORA PSI
Cripps RC, Güntay S, Jäckel B
The predicted effects of selected Phebus FPT1 sump constituents on iodine volatility
Nuclear Engineering and Design. 2014; 272: 99-108. https://doi.org/10.1016/j.nucengdes.2014.02.019
DORA PSI
Fernandez-Moguel L, Bals C, Beuzet E, Bratfisch C, Coindreau O, Hózer Z, et al.
SARNET2 benchmark on air ingress experiments QUENCH-10, -16
Annals of Nuclear Energy. 2014; 74: 12-23. https://doi.org/10.1016/j.anucene.2014.05.013
DORA PSI
Fleurot J, Lindholm I, Kononen N, Ederli S, Jaeckel B, Kaliatka A, et al.
Synthesis of spent fuel pool accident assessments using severe accident codes
Annals of Nuclear Energy. 2014; 74: 58-71. https://doi.org/10.1016/j.anucene.2014.07.011
DORA PSI
Ihalainen M, Lind T, Arffman A, Torvela T, Jokiniemi J
Break-Up and bounce of TiO₂ agglomerates by impaction
Aerosol Science and Technology. 2014; 48(1): 31-41. https://doi.org/10.1080/02786826.2013.852155
DORA PSI
Ihalainen M, Lind T, Ruusunen J, Tiitta P, Lähde A, Torvela T, et al.
Experimental study on bounce of submicron agglomerates upon inertial impaction
Powder Technology. 2014; 268: 203-209. https://doi.org/10.1016/j.powtec.2014.08.029
DORA PSI
Klein-Heßling W, Sonnenkalb M, Jacquemain D, Clément B, Raimond E, Dimmelmeier H, et al.
Conclusions on severe accident research priorities
Annals of Nuclear Energy. 2014; 74: 4-11. https://doi.org/10.1016/j.anucene.2014.07.015
DORA PSI
Mukin RV
Modeling of bubble coalescence and break-up in turbulent bubbly flow
International Journal of Multiphase Flow. 2014; 62: 52-66. https://doi.org/10.1016/j.ijmultiphaseflow.2014.02.008
DORA PSI
Papini D, Adamsson C, Andreani M, Prasser H-M
Assessment of GOTHIC and TRACE codes against selected PANDA experiments on a Passive Containment Condenser
Nuclear Engineering and Design. 2014; 278: 542-557. https://doi.org/10.1016/j.nucengdes.2014.08.007
DORA PSI
Ruusunen J, Ihalainen M, Koponen T, Torvela T, Tenho M, Salonen J, et al.
Controlled oxidation of iron nanoparticles in chemical vapour synthesis
Journal of Nanoparticle Research. 2014; 16(2): 2270 (11 pp.). https://doi.org/10.1007/s11051-014-2270-0
DORA PSI
Toggweiler M, Adelmann A, Arbenz P, Yang J
A novel adaptive time stepping variant of the Boris-Buneman integrator for the simulation of particle accelerators with space charge
Journal of Computational Physics. 2014; 273: 255-267. https://doi.org/10.1016/j.jcp.2014.05.008
DORA PSI
Birchley J, Güntay S
Significance of Phébus-FP results for plant safety in Switzerland
Annals of Nuclear Energy. 2013; 61: 206-214. https://doi.org/10.1016/j.anucene.2013.02.032
DORA PSI
Bosshard C, Dehbi A, Deville M, Leriche E, Puragliesi R, Soldati A
Large eddy simulation of the differentially heated cubic cavity flow by the spectral element method
Computers and Fluids. 2013; 86: 210-227. https://doi.org/10.1016/j.compfluid.2013.07.007
DORA PSI
Dehbi A, Badreddine H
CFD prediction of mixing in a steam generator mock-up: comparison between full geometry and porous medium approaches
Annals of Nuclear Energy. 2013; 58: 178-187. https://doi.org/10.1016/j.anucene.2013.03.019
DORA PSI
Dehbi A
On the adequacy of wall functions to predict condensation rates from steam-noncondensable gas mixtures
Nuclear Engineering and Design. 2013; 265: 25-34. https://doi.org/10.1016/j.nucengdes.2013.07.014
DORA PSI
Dehbi A, Janasz F, Bell B
Prediction of steam condensation in the presence of noncondensable gases using a CFD-based approach
Nuclear Engineering and Design. 2013; 258: 199-210. https://doi.org/10.1016/j.nucengdes.2013.02.002
DORA PSI
Fernandez-Moguel L, Birchley J
Analysis of QUENCH-10 and -16 air ingress experiments with SCDAPSim3.5
Annals of Nuclear Energy. 2013; 53: 202-212. https://doi.org/10.1016/j.anucene.2012.08.030
DORA PSI
Freixa J, Kim T-W, Manera A
Post-test thermal-hydraulic analysis of two intermediate LOCA tests at the ROSA facility including uncertainty evaluation
Nuclear Engineering and Design. 2013; 264: 153-160. https://doi.org/10.1016/j.nucengdes.2013.02.023
DORA PSI
Rycroft CH, Dehbi A, Lind T, Güntay S
Granular flow in pebble-bed nuclear reactors: scaling, dust generation, and stress
Nuclear Engineering and Design. 2013; 265: 69-84. https://doi.org/10.1016/j.nucengdes.2013.07.010
DORA PSI
Yang JJ, Adelmann A, Barletta W, Calabretta L, Calanna A, Campo D, et al.
Beam dynamics simulation for the high intensity DAEδALUS cyclotrons
Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment. 2013; 704: 84-91. https://doi.org/10.1016/j.nima.2012.12.050
DORA PSI
Ammar Y, Dehbi A, Reeks MW
Break-up of aerosol agglomerates in highly turbulent gas flow
Flow, Turbulence and Combustion. 2012; 89(3): 465-489. https://doi.org/10.1007/s10494-012-9398-8
DORA PSI
Andreani M, Bittermann D, Marsault P, Antoni O, Keresztúri A, Schlagenhaufer M, et al.
Evaluation of a preliminary safety concept for the HPLWR
Progress in Nuclear Energy. 2012; 55: 68-77. https://doi.org/10.1016/j.pnucene.2011.11.004
DORA PSI
Aounallah Y
Simulation of HALDEN IFA-650 loss-of-coolant accidents tests with TRACE
Kerntechnik. 2012; 77(5): 316-323. https://doi.org/10.3139/124.110214
DORA PSI
Birchley J, Fernandez-Moguel L
Simulation of air oxidation during a reactor accident sequence: part 1 - phenomenology and model development
Annals of Nuclear Energy. 2012; 40(1): 163-170. https://doi.org/10.1016/j.anucene.2011.10.019
DORA PSI
Bottomley D, Stuckert J, Hofmann P, Tocheny L, Hugon M, Journeau C, et al.
Severe accident research in the core degradation area: an example of effective international cooperation between the European Union (EU) and the Commonwealth of Independent States (CIS) by the International Science and Technology Center
Nuclear Engineering and Design. 2012; 252: 226-241. https://doi.org/10.1016/j.nucengdes.2012.07.006
DORA PSI
Fernandez-Moguel L, Birchley J
Simulation of air oxidation during a reactor accident sequence: part 2 - analysis of PARAMETER-SF4 air ingress experiment using RELAP5/SCDAPSIM
Annals of Nuclear Energy. 2012; 40(1): 141-152. https://doi.org/10.1016/j.anucene.2011.10.018
DORA PSI
Freixa J, Manera A
Remarks on consistent development of plant nodalizations: an example of application to the ROSA integral test facility
Science and Technology of Nuclear Installations. 2012; 2012: 158617 (17 pp.). https://doi.org/10.1155/2012/158617
DORA PSI
Freixa J, Kim T-W, Manera A
Thermal-hydraulic analysis of an intermediate LOCA test at the ROSA facility including uncertainty evaluation
Nuclear Engineering and Design. 2012; 249: 97-103. https://doi.org/10.1016/j.nucengdes.2011.08.061
DORA PSI
Girault N, Bosland L, Dickinson S, Funke F, Güntay S, Herranz LE, et al.
LWR severe accident simulation: iodine behaviour in FPT2 experiment and advances on containment iodine chemistry
Nuclear Engineering and Design. 2012; 243: 371-392. https://doi.org/10.1016/j.nucengdes.2011.11.011
DORA PSI
Ihalainen M, Lind T, Torvela T, Lehtinen KEJ, Jokiniemi J
A method to study agglomerate breakup and bounce during impaction
Aerosol Science and Technology. 2012; 46(9): 990-1001. https://doi.org/10.1080/02786826.2012.685663
DORA PSI
Kim T, Petrov V, Manera A, Lo S
Analysis of void fraction distribution and departure from nucleate boiling in single subchannel and bundle geometries using subchannel, system, and computational fluid dynamics codes
Science and Technology of Nuclear Installations. 2012; 2012: 746467 (20 pp.). https://doi.org/10.1155/2012/746467
DORA PSI
Kim TW, Dang VN, Zimmermann MA, Manera A
Quantitative evaluation of change in core damage frequency by postulated power uprate: medium-break loss-of-coolant-accidents
Annals of Nuclear Energy. 2012; 47: 69-80. https://doi.org/10.1016/j.anucene.2012.04.021
DORA PSI
Kozmenkov Y, Rohde U, Manera A
Validation of the RELAP5 code for the modeling of flashing-induced instabilities under natural-circulation conditions using experimental data from the CIRCUS test facility
Nuclear Engineering and Design. 2012; 243: 168-175. https://doi.org/10.1016/j.nucengdes.2011.10.053
DORA PSI
Sharabi M, Freixa J
Analysis of the ISP-50 Direct Vessel Injection SBLOCA in the ATLAS facility with the RELAP5/MOD3.3 code
Nuclear Engineering and Technology. 2012; 44(7): 709-718. https://doi.org/10.5516/NET.02.2012.712
DORA PSI
Adamsson C, Le Corre J-M
Modeling and validation of a mechanistic tool (MEFISTO) for the prediction of critical power in BWR fuel assemblies
Nuclear Engineering and Design. 2011; 241(8): 2843-2858. https://doi.org/10.1016/j.nucengdes.2011.01.033
DORA PSI
Barten W, Jasiulevicius A, Zerkak O, Macian-Juan R
Analysis of the umsichtwater hammer benchmark experiment 329 using trace and RELAP5
Multiphase Science and Technology. 2011; 23(1): 1-27. https://doi.org/10.1615/MultScienTechn.v23.i1.10
DORA PSI
Bertolotto D, Manera A, Macián-Juan R, Chawla R
Improvement of the one-dimensional dissolved-solute convection equation using the QUICKEST-ULTIMATE algorithm
Nuclear Engineering and Design. 2011; 241(1): 245-256. https://doi.org/10.1016/j.nucengdes.2010.10.021
DORA PSI
Chylarecka D, Kim TK, Tarafder K, Müller K, Gödel K, Czekaj I, et al.
Indirect magnetic coupling of manganese porphyrin to a ferromagnetic cobalt substrate
Journal of Physical Chemistry C. 2011; 115(4): 1295-1301. https://doi.org/10.1021/jp106822s
DORA PSI
Freixa J, Manera A
Verification of a TRACE EPR™ model on the basis of a scaling calculation of an SBLOCA ROSA test
Nuclear Engineering and Design. 2011; 241(3): 888-896. https://doi.org/10.1016/j.nucengdes.2010.12.016
DORA PSI
Nikitin K, Manera A
Analysis of an ADS spurious opening event at a BWR/6 by means of the TRACE code
Nuclear Engineering and Design. 2011; 241(6): 2240-2247. https://doi.org/10.1016/j.nucengdes.2011.03.021
DORA PSI
Perez M, Reventos F, Batet L, Guba A, Tóth I, Mieusset T, et al.
Uncertainty and sensitivity analysis of a LBLOCA in a PWR nuclear power plant: results of the phase V of the BEMUSE programme
Nuclear Engineering and Design. 2011; 241(10): 4206-4222. https://doi.org/10.1016/j.nucengdes.2011.08.019
DORA PSI
Petrov V, Manera A
Effect of pump-induced cold-leg swirls on the flow field in the RPV of the EPR^TM: CFD investigations and comparison with experimental results
Nuclear Engineering and Design. 2011; 241(5): 1478-1485. https://doi.org/10.1016/j.nucengdes.2011.02.027
DORA PSI
Vinai P, Macian-Juan R, Chawla R
Propagation of void fraction uncertainty measures in the RETRAN-3D simulation of the Peach Bottom turbine trip
Annals of Nuclear Energy. 2011; 38(2-3): 358-370. https://doi.org/10.1016/j.anucene.2010.10.007
DORA PSI
Zerkak O, Ferroukhi H
Vessel coolant mixing effects on a PWR Main Steam Line Break transient
Annals of Nuclear Energy. 2011; 38(1): 60-71. https://doi.org/10.1016/j.anucene.2010.08.016
DORA PSI
Aounallah Y
Development of a wide-range pre-CHF convective boiling correlation
Journal of Nuclear Science and Technology. 2010; 47(4): 357-366. https://doi.org/10.3327/jnst.47.357
DORA PSI
Bechta SV, Krushinov EV, Vitol SA, Khabensky VB, Kotova SY, Sulatsky AA, et al.
Influence of corium oxidation on fission product release from molten pool
Nuclear Engineering and Design. 2010; 240(5): 1229-1241. https://doi.org/10.1016/j.nucengdes.2010.01.008
DORA PSI
Freixa J, Manera A
Analysis of an RPV upper head SBLOCA at the ROSA facility using TRACE
Nuclear Engineering and Design. 2010; 240(7): 1779-1788. https://doi.org/10.1016/j.nucengdes.2010.02.007
DORA PSI
Pérez M, Reventós F, Batet L, Pericas R, Toth I, Bazin P, et al.
Main Results of phase IV BEMUSE project: simulation of LBLOCA in an NPP
Science and Technology of Nuclear Installations. 2010; 2010: 219294 (9 pp.). https://doi.org/10.1155/2010/219294
DORA PSI
Rohde M, Marcel CP, Manera A, Van der Hagen THJJ, Shiralkar B
Investigating the ESBWR stability with experimental and numerical tools: a comparative study
Nuclear Engineering and Design. 2010; 240(2): 375-384. https://doi.org/10.1016/j.nucengdes.2008.01.016
DORA PSI
Walker C, Manera A, Niceno B, Simiano M, Prasser HM
Steady-state RANS-simulations of the mixing in a T-junction
Nuclear Engineering and Design. 2010; 240(9): 2107-2115. https://doi.org/10.1016/j.nucengdes.2010.05.056
DORA PSI

Conclusions on severe accident research priorities
W. Klein-Heßling, M. Sonnenkalb, D. Jacquemain, B. Clément, E. Raimond, H. Dimmelmeier, G. Azarian, G. Ducros, C. Journeau, L.E. Herranz Puebla, A. Schumm, A. Miassoedov, I. Kljenak, G. Pascal, S. Bechta, S. Güntay, M.K. Koch, I. Ivanov, A. Auvinen, I. Lindholm
Annals of Nuclear Energy 74, 4
http://dx.doi.org/10.1016/j.anucene.2014.07.015

Synthesis of spent fuel pool accident assessments using severe accident codes
J. Fleurot, I. Lindholm, N. Kononen, B.S. Jäckel, A. Kaliatka, J. Duspiva, M. Steinbrück, T. Hollands
Annals of Nuclear Energy 74, 58
http://dx.doi.org/10.1016/j.anucene.2014.07.011

Experimental study on bounce of submicron agglomerates upon inertial impaction
M. Ihalainen, T.M. Lind, J. Ruusunen, P. Tiitta, A. Lahde, T. Torvela, J. Jokiniemi
Powder Technology 268, 203
http://dx.doi.org/10.1016/j.powtec.2014.08.029

Significance of Phébus-FP results for plant safety in Switzerland
J.C. Birchley, S. Güntay
Annals of Nuclear Energy 61, 206
http://dx.doi.org/10.1016/j.anucene.2013.02.032

A Method to Study Agglomerate Breakup and Bounce During Impaction
M. Ihalainen, T.M. Lind, T. Torvela, K.E.J. Lehtinen, J.K. Jokiniemi
Aerosol Science and Technology 46, 990
http://dx.doi.org/10.1080/02786826.2012.685663

Severe accident research in the core degradation area: An example of effective international cooperation between the European Union (EU) and the Commonwealth of Independent States (CIS) by the International Science and Technology Center
D. Bottomley, J. Stuckert, P. Hofmann, L. Tocheny, M. Hugon, C. Journeau, B. Clement, S. Weber, S. Güntay, Z. Hozer, L.E. Herranz, A. Schumm, F. Oriolo, E. Altstadt, M. Krause, M. Fischer, V.B. Khabensky, S.V. Bechta, M.S. Veshchunov, A.V. Palagin, A.E. Kiselev, V.I. Nalivaev, A.V. Goryachev, V. Zhdanov, V. Baklanov
Nuclear Engineering and Design 252, 226
http://dx.doi.org/10.1016/j.nucengdes.2012.07.006

LWR severe accident simulation: Iodine behaviour in FPT2 experiment and advances on containment iodine chemistry
N. Girault, L. Bosland, S. Dickinson, F. Funke, S. Güntay, L.E. Herranz, D. Powers
Nuclear Engineering and Design 243, 371
http://dx.doi.org/10.1016/j.nucengdes.2011.11.011

Towards possible opportunities in nuclear materials science and technology at an X-ray free electron laser research facility
A. Froideval, A. Badillo, J. Bertsch, S. Churakov, R. Dahn, C. Degueldre, T.M. Lind, D. Paladino, B.D. Patterson
Journal of Nuclear Materials 416, 242
http://dx.doi.org/10.1016/j.nucmat.2011.01.124

The PSIodine Code: A computer program to model experimental data on iodine and other species in irradiated CsI solutions sparged with argon, air, or nitrous oxide
R.C. Cripps, S. Güntay, B.S. Jäckel
Nuclear Engineering and Design 241, 4306
http://dx.doi.org/10.1016/j.nucengdes.2011.08.010

Sustainable integration of EU research in severe accident phenomenology and management
J.P. Van Dorsselaere, T. Albiol, B. Chaumont, T.J. Haste, C. Journeau, L. Meyer, B.R. Sehgal, B. Schwinges, D. Beraha, A. Annunziato, R. Zeyen
Nuclear Engineering and Design 241, 3451
http://dx.doi.org/10.1016/j.nucengdes.2011.01.053

On the radiolysis of iodide, nitrate and nitrite ions in aqueous solution: An experimental and modelling study
R.C. Cripps, B.S. Jäckel, S. Güntay
Nuclear Engineering and Design 241, 3333
http://dx.doi.org/10.1016/j.nucengdes.2011.06.031

Experimental and calculation results of the integral reflood test QUENCH-15 with ZIRLO (TM) cladding tubes in comparison with results of previous QUENCH tests
J. Stuckert, J.C. Birchley, M. Große, B.S. Jäckel, M. Steinbrück
Nuclear Engineering and Design 241, 3224
http://dx.doi.org/10.1016/j.nucengdes.2011.05.004

CFD simulation of particle deposition on an array of spheres using an Euler/Lagrange approach
A. Dehbi, S. Martin
Nuclear Engineering and Design 241, 3121
http://dx.doi.org/10.1016/j.nucengdes.2011.05.031

Aerosol retention in the flooded steam generator bundle during SGTR
T.M. Lind, A. Dehbi, S. Güntay
Nuclear Engineering and Design 241, 357
http://dx.doi.org/10.1016/j.nucengdes.2010.10.025

Analyses of the Phebus FPT3 Experiment using the Severe Accident Codes ATHLET-CD, ICARE/CATHARE and MELCOR
G. Repetto, O. De Luze, T. Drath, M.K. Koch, T. Hollands, K. Trambauer, C. Bals, H. Austregesilo, J.C. Birchley
Nuclear Technology 176, 352

The Once-through Mode of Steam Generator Refulx Condensation in Loss-of-Coolant Accident Scenarios
Y. Liao, S. Güntay, D.J. Suckow
Nuclear Technology 175, 510

Validation of the Langevin particle dispersion model against experiments on turbulent mixing in a T-junction
A. Dehbi, F. de Crécy
Powder Technology 206, 312
http://dx.doi.org/10.1016/j.powtec.2010.09.036

DNS of buoyancy-driven flows and Lagrangian particle tracking in a square cavity at high Rayleigh numbers
R. Puragliesi, A. Dehbi, E. Leriche, A. Soldati, M.O. Deville
International Journal of Heat and Fluid Flow 32, 915
http://dx.doi.org/10.1016/j.ijheatfluidflow.2011.06.007

Prediction of extrathoracic aerosol deposition using RANS-Random Walk and LES approaches
A. Dehbi
Aerosol Science and Technology 45, 555
http://dx.doi.org/10.1080/02786826.2010.550962

Experimental and calculation results of the integral reflood test QUENCH-14 with M5 (R) cladding tubes
J. Stuckert, J.C. Birchley, M. Große, B.S. Jäckel, M. Steinbrück
Annals of Nuclear Energy 37, 1036 (2010)
http://dx.doi.org/10.1016/j.anucene.2010.04.015

Local nonsimilarity method for the two-phase boundary layer in mixed convection laminar film condensation
Y. Liao, S. Güntay, K. Vierow
International Journal for Heat and Mass Transfer 46, 447 (2010)
http://dx.doi.org/10.1007/s00231-010-0588-4

Aerosol behavior during SIC control rod failure in QUENCH-13 test
T.M. Lind, A.P. Csordas, I. Nagy, J. Stuckert
Journal of Nuclear Materials 397, 92 (2010)
http://dx.doi.org/10.1016/j.nucmat.2009.12.013

Implementation of a generalized diffusion layer model for condensation into MELCOR
K. Hogan, Y. Liao, B. Beeny, K. Vierow, R.Jr. Cole, L.L. Humphries, R.O. Gauntt
Nuclear Engineering and Design 240, 3202 (2010)
http://dx.doi.org/10.1016/j.nucengdes.2010.05.059

De-agglomeration mechanisms of TiO2 aerosol agglomerates in PWR steam generator tube rupture conditions
T.M. Lind, Y. Ammar, A. Dehbi, S. Güntay
Nuclear Engineering and Design 240, 2046 (2010)
http://dx.doi.org/10.1016/j.nucengdes.2010.03.002

Accident management following loss-of-coolant accidents during cooldown in a Westinghouse two-loop PWR
T.J. Haste, J.C. Birchley, M. Richner
Nuclear Engineering and Design 240, 1599 (2010)
http://dx.doi.org/10.1016/j.nucengdes.2010.02.006

Influence of corium oxidation on fission product release from molten pool
S.V. Bechta, E.V. Krushinov, S.A. Vitol, V.B. Khabensky, S.Y. Kotova, A.A. Sulatsky, V.V. Gusarov, V.I. Almyashev, G. Ducros, C. Journeau, D. Bottomley, B. Clement, L.E. Herranz, S. Güntay, K. Trambauer, A. Auvinen, V.V. Bezlepkin
Nuclear Engineering and Design 240, 1229 (2010)
http://dx.doi.org/10.1016/j.nucengdes.2010.01.008

Benchmark study on fuel bundle degradation in the Pebus FPT2 test using state-of-the-art severe accident analysis codes
B. Tóth, A. Bieliauskas, G. Bandini, J.C. Birchley, H. Wada, J. Hohorst, C. Jamond, K. Trambauer
Nuclear Technology 169, 81 (2010)
http://epubs.ans.org/download/?a=9354

Validation against DNS statistics of the normalized Langevin model for particletransport in turbulent channel flows
A. Dehbi
Powder Technology 200, 60 (2010)
http://dx.doi.org/10.1016/j.powtec.2010.02.009

Monodisperse fine aerosol generation using fluidized bed
T.M. Lind, S. Danner, S. Güntay
Powder Technology 199, 232 (2010)
http://dx.doi.org/10.1016/j.powtec.2010.01.011

Progress in understanding key aerosol issues
L.E. Herranz, J. Ball, A. Auvinen, D. Bottomley, A. Dehbi, C. Housiadas, P. Piluso, V. Layly, F. Parozzi, M. Reeks
Progress in Nuclear Energy 52, 120 (2010)
http://dx.doi.org/10.1016/j.pnucene.2009.09.013

Recent advances in understanding ruthenium behaviour under air-ingress conditions during a PWR severe accident
P. Giordano, A. Auvinen, G. Brillant, J. Colombani, N. Davidovich, R. Dickson, T.J. Haste, T. Kärkelä, J.S. Lamy, C. Mun, D. Ohai , Y. Pontillon, M. Steinbrück, N. Vér
Progress in Nuclear Energy 52, 109 (2010)
http://dx.doi.org/10.1016/j.pnucene.2009.09.011

Understanding the behaviour of absorber elements in silver-indium-cadmium control rods during PWR severe accident sequences
R. Dubourg, H. Austregesilo, C. Bals, M. Barrachin, J.C. Birchley, T.J. Haste, J.S. Lamy, T.M. Lind, B. Maliverney, C. Marchetto, A. Pinter, M. Steinbrück, J. Stuckert, K. Trambauer, A. Vimi
Progress in Nuclear Energy 52, 97 (2010)
http://dx.doi.org/10.1016/j.pnucene.2009.09.012

B₄C oxidation modelling in severe accident codes: Applications to PHEBUS and QUENCH experiments
G. Repetto, O. De Luze, N. Seiler, K. Trambauer, H. Austregesilo, J.C. Birchley, S. Ederli, J.S. Lamy, B. Maliverney, T. Drath, T. Hollands
Progress in Nuclear Energy 52, 37 (2010)
http://dx.doi.org/10.1016/j.pnucene.2009.09.017

High-temperature oxidation and quench behaviour of Zircaloy-4 and E110 cladding alloys
M. Steinbrück, J.C. Birchley, A.V. Boldyrev, A.V. Goryachev, M. Grosse, T.J. Haste, Z. Hózer, A.E. Kisselev, V.I. Nalivaev, V.P. Semishkin, L. Sepold, J. Stuckert, N. Vér, M.S. Veshchunov
Progress in Nuclear Energy 52, 19 (2010)
http://dx.doi.org/10.1016/j.pnucene.2009.07.012

Ranking of severe accident research priorities
B. Schwinges, C. Journeau, T.J. Haste, L. Meyerd, W. Tromm, K. Trambauer
Progress in Nuclear Energy 52, 11 (2010)
http://dx.doi.org/10.1016/j.pnucene.2009.09.006

SARNET: Severe accident research network of excellence
T. Albiol, J.P. Van Dorsselaere, B. Chaumont, T.J. Haste, C. Journeau, L. Meyer, B.R. Sehgal, B. Schwinges, D. Beraha, A. Annunziato, R. Zeyen
Progress in Nuclear Energy* 52, 2 (2010)
http://dx.doi.org/10.1016/j.pnucene.2009.07.011

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2005-2009

Bertolotto D, Manera A, Frey S, Prasser H-M, Chawla R
Single-phase mixing studies by means of a directly coupled CFD/system-code tool
Annals of Nuclear Energy. 2009; 36(3): 310-316. https://doi.org/10.1016/j.anucene.2008.11.027
DORA PSI
Ferroukhi H, Zerkak O, Chawla R
Cross-section modelling effects on pressurised water reactor main steam line break analyses
Annals of Nuclear Energy. 2009; 36(8): 1184-1200. https://doi.org/10.1016/j.anucene.2009.04.006
DORA PSI
Kato Y, Tsuzuki N, Nikitin K, Ishizuka T
Advanced microchannel heat exchanger with S-shaped fins
Journal of Nuclear Science and Technology. 2009; 46(5): 403-412. https://doi.org/10.1080/18811248.2007.9711547
DORA PSI
Manera A, Ozar B, Paranjape S, Ishii M, Prasser H-M
Comparison between wire-mesh sensors and conductive needle-probes for measurements of two-phase flow parameters
Nuclear Engineering and Design. 2009; 239(9): 1718-1724. https://doi.org/10.1016/j.nucengdes.2008.06.015
DORA PSI
Tsuzuki N, Kato Y, Nikitin K, Ishizuka T
Advanced microchannel heat exchanger with S-shaped fins
Journal of Nuclear Science and Technology. 2009; 46(5): 403-412. https://doi.org/10.3327/jnst.46.403
DORA PSI
Aounallah Y
A separate-effect-based new appraisal of convective boiling and its suppression
Journal of Nuclear Science and Technology. 2008; 45(2): 149-159. https://doi.org/10.1080/18811248.2008.9711424
DORA PSI
Aounallah Y
A separate-effect-based new appraisal of convective boiling and its suppression
Journal of Nuclear Science and Technology. 2008; 45(2): 149-159. https://doi.org/10.3327/jnst.45.149
DORA PSI
Barten W, Jasiulevicius A, Manera A, Macian-Juan R, Zerkak O
Analysis of the capability of system codes to model cavitation water hammers: simulation of UMSICHT water hammer experiments with TRACE and RELAP5
Nuclear Engineering and Design. 2008; 238(4): 1129-1145. https://doi.org/10.1016/j.nucengdes.2007.10.004
DORA PSI
Barten W, Manera A, Macian-Juan R
One- and two-dimensional standing pressure waves and one-dimensional travelling pulses using the US-NRC nuclear systems analysis code TRACE
Nuclear Engineering and Design. 2008; 238(10): 2568-2582. https://doi.org/10.1016/j.nucengdes.2008.05.004
DORA PSI
Macian R, Zimmermann MA, Chawla R
Statistical uncertainty analysis applied to fuel depletion calculations
Journal of Nuclear Science and Technology. 2007; 44(6): 875-885. https://doi.org/10.3327/jnst.44.875
DORA PSI
Vinai P, Macian-Juan R, Chawla R
A statistical methodology for quantification of uncertainty in best estimate code physical models
Annals of Nuclear Energy. 2007; 34(8): 628-640. https://doi.org/10.1016/j.anucene.2007.03.003
DORA PSI
Zerkak O, Coddington P, Eitschberger H
Analysis of the Leibstadt power plant condensate and feedwater systems during selected operational transients
Nuclear Engineering and Design. 2007; 237(11): 1195-1208. https://doi.org/10.1016/j.nucengdes.2007.01.011
DORA PSI
Barten W, Coddington P, Ferroukhi H
RETRAN-3D analysis of the base case and the four extreme cases of the OECD/NRC Peach Bottom 2 Turbine Trip benchmark
Annals of Nuclear Energy. 2006; 33(2): 99-118. https://doi.org/10.1016/j.anucene.2005.09.011
DORA PSI
Jasiulevičius A, Sehgal BR
Experimental investigation of debris bed quenching with non-condensable gas release
Energetika. 2006; 3(1): 1-8.
DORA PSI
Lucas D, Krepper E, Prasser H-M, Manera A
Investigations on the stability of the flow characteristics in a bubble column
Chemical Engineering and Technology. 2006; 29(9): 1066-1072. https://doi.org/10.1002/ceat.200600150
DORA PSI

Cfd4nrs With A Focus On Experimental And Cmfd Investigations Of Bubbly Flows
G Yadigaroglu, M Simiano, R Milenkovic, J Kubasch, M Milelli, R Zboray, Cachard De, Smith F, Lakehal B, Sigg D,
Nuclear Engineering And Design 238, 771-785 (2008). (2009)
http://dx.doi.org/10.1016/j.nucengdes.2007.02.047

AgInCd control rod failure in the QUENCH-13 bundle test
L. Sepold, T.M. Lind, A.P. Csordas, U. Stegmaier, M. Steinbrück, J. Stuckert
Annals of Nuclear Energy 36, 1349 (2009)
http://dx.doi.org/10.1016/j.anucene.2009.06.020

Experimental and post-test calculation results of the integral reflood test QUENCH-12 with a VVER-type bundle
J. Stuckert, J.C. Birchley, M. Große, T.J. Haste, L. Sepold, M. Steinbrück
Annals of Nuclear Energy* 36, 183 (2009)
http://dx.doi.org/10.1016/j.anucene.2008.11.024

Transition from natural to mixed convection for steam-gas flow condensing along a vertical plate
Y. Liao, K. Vierow, A. Dehbi, S. Güntay
International Journal for Heat and Mass Transfer 52, 366 (2009)
http://dx.doi.org/10.1016/j.ijheatmasstransfer.2008.06.008

A stochastic Langevin model of turbulent particle dispersion in the presence of thermophoresis
A. Dehbi
International Journal of Multiphase Flow 35, 219 (2009)
http://dx.doi.org/10.1016/j.ijmultiphaseflow.2009.11.006

Reflux condensation of flowing vapor and non-condensable gases counter-current to laminar liquid film in a vertical tube
Y. Liao, S. Güntay, D.J. Suckow, A. Dehbi
Nuclear Engineering and Design 239, 2409 (2009)
http://dx.doi.org/10.1016/j.nucengdes.2009.07.006

Potential steam generator tube rupture in the presence of severe accident thermal challenge and tube flaws due to foreign object wear
Y. Liao, S. Güntay
Nuclear Engineering and Design 239, 1128 (2009)
http://dx.doi.org/10.1016/j.nucengdes.2009.02.003

Separate-effect tests on zirconium cladding degradation in air ingress situations
C. Duriez, M. Steinbrück, D. Ohai, T. Meleg, J.C. Birchley, T.J. Haste
Nuclear Engineering and Design 239, 244 (2009)
http://dx.doi.org/10.1016/j.nucengdes.2008.10.017

Turbulent particle dispersion in arbitrary wall-bounded geometries: A coupled CFD-Langevin-equation based approach
A. Dehbi
International Journal of Multiphase Flow 34, 819 (2008)
http://dx.doi.org/10.1016/j.ijmultiphaseflow.2008.03.001

Effects of chlorine and sulphur on particle formation in wood combustion performed in a laboratory scale reactor
O. Sippula, T.M. Lind, J.K. Jokiniemi
Journal of Fuel 87, 2425 (2008)
http://dx.doi.org/10.1016/j.fuel.2008.02.004

A simple probabilistic approach to evaluate radioiodine behavior at severe accidents: Application to PHEBUS test FPT1
A. Rýdl
Nuclear Engineering and Design* 238, 2387 (2008)
http://dx.doi.org/10.1016/j.nucengdes.2008.02.027

Accident management following loss of residual heat removal during mid-loop operation in a Westinghouse two-loop PWR
J.C. Birchley, T.J. Haste, M. Richner
Nuclear Engineering and Design 238, 2173 (2008)
http://dx.doi.org/10.1016/j.nucengdes.2008.02.009

A CFD model for particle dispersion in turbulent boundary layer flows
A. Dehbi
Nuclear Engineering and Design 238, 707 (2008)
http://dx.doi.org/10.1016/j.nucengdes.2007.02.055

Validation of severe accident codes on the Phebus fission product tests in the framework of the PHEBEN-2 project
K. Müller, S. Dickinson, C. de Pascale, N. Girault, L.E. Herranz, F. de Rosa, G. Henneges, J. Langhans, C. Housiadas, V. Wichers, A. Dehbi, S. Paci, F. Martin-Fuentes, I. Turcu, I. Ivanov, B. Toth, L.G. Horvath
Nuclear Technology 163, 209 (2008)

Fine particle and trace element emissions from waste combustion - Comparison of fluidized bed and grate firing
T.M. Lind, J. Hokkinen, J.K. Jokiniemi
Fuel Processing Technology 88, 737 (2007)
http://dx.doi.org/10.1016/j.fuproc.2007.03.004

Radiochemical studies of the retention of volatile iodine in aqueous solutions
S. Güntay, R.C. Cripps, B.S. Jäckel, H. Bruchertseifer
Journal of Radioanalytical and Nuclear Chemistry 273, 557 (2007)
http://dx.doi.org/10.1007/s10967-007-0909-3

Major challenges to modeling aerosol retention near a tube breach during steam generator tube rupture sequences
L.E. Herranz, C. Lopez del Pra, A. Dehbi
Nuclear Technology 158, 83 (2007)

Benchmark study on fuel bundle degradation in the Phebus FPT3 test using the severe accident codes ATHLET-CD, ICARE2, and MELCOR
B. Toth, K. Müller, J.C. Birchley, H. Wada, C. Jamond, K. Trambauer
Nuclear Technology 157, 132 (2007)

Effect of chlorine and sulfur on fine particle formation in pilot-scale CFBC of biomass
T.M. Lind, E.L. Kauppinen, J. Hokkinen, J.K. Jokiniemi, M. Orjala, M. Aurela, R. Hillamo
Energy and Fuels 20, 61 (2006)
http://dx.doi.org/10.1021/ef050122i

Electrostatic precipitator performance and trace element emissions from two Kraft recovery boilers
T.M. Lind, J. Hokkinen, J.K. Jokiniemi, R. Hillamo, U. Makkonen, A. Raukola, J. Rintanen, K. Saviharju
Environmental Science & Technology 40, 584 (2006)
http://dx.doi.org/10.1021/es0503027

MELCOR/MACCS simulation of the TMI-2 severe accident and initial recovery phases, off-site fission product release and consequences
T.J. Haste, J.C. Birchley, E.G. Cazzoli, J. Vitazkova
Nuclear Engineering and Design 236, 1099 (2006)
http://dx.doi.org/10.1002/j.nucengdes.2005.11.012

Open-Pore Organic Material for Retaining Radioactive I2 and CH3I
T. Hertzsch, C. Gervais, J. Hulliger, B.S. Jäckel, S. Güntay, H. Bruchertseifer, A. Neels
Advanced Functional Materials 16, 268 (2005)
http://dx.doi.org/10.1002/adfm.200500245

Development of semi-automated system for preparation of Re-188 aqueous solutions of high and reproducible activity concentrations
B.S. Jäckel, R.C. Cripps, Güntay, H. Bruchertseifer
Applied Radiation and Isotopes 63, 299 (2005)
http://dx.doi.org/10.1016/j.apradiso.2005.04.009

Iodine behaviour during a severe accident in a nuclear power plant
S. Güntay, R.C. Cripps, B.S. Jäckel, H. Bruchertseifer
Chimia 59, 957 (2005)
http://dx.doi.org/10.2533/000942905777675453

Phebus-FP: Results and significance for plant safety in Switzerland
J.C. Birchley, T.J. Haste, H. Bruchertseifer, R.C. Cripps, S. Güntay, B.S. Jäckel
Nuclear Engineering and Design 235, 1607 (2005)
http://dx.doi.org/10.1016/j.nucengdes.2005.02.018

Steam generator tube rupture (SGTR) scenarios
A. Auvinen, J.K. Jokiniemi, A. Lahde, T. Routamo, P. Lundstrom, H. Tuomisto, J. Dienstbier, S. Güntay, D.J. Suckow, A. Dehbi, M. Slootman, L.E. Herranz, V. Peyres, J. Polo
Nuclear Engineering and Design 235, 457 (2005)
http://dx.doi.org/10.1016/j.nucengdes.2004.08.060

European expert network for the reduction of uncertainties in severe accident safety issues (EURSAFE)
D. Magallon, A. Mailliat, J.M. Seiler, K. Athken, H. Sjovall, S. Dickinson, J. Jakab, L. Meyer, M. Buerger, K. Trambauer, L. Fickert, B.R. Sehgal, Z. Hozer, J. Bagues, F. Martin-Fuentes, R. Zeyen, A. Annunziato, M. El-Shanawany, S. Güntay, C. Tinkler, B. Turland, L.E. Herranz
Nuclear Engineering and Design 235, 309 (2005)
http://dx.doi.org/10.1016/j.nucengdes.2004.08.042

Core loss during a severe accident (COLOSS)
B. Adroguer, F. Bertrand, P. Chatelard, N. Cocuaud, J.P. van Dorsselaere, L. Bellenfant, D. Knocke, D. Bottomley, V. Vrtilkova, L. Belovsky, K. Müller, W. Hering, C. Homann, W. Krauss, A. Miassoedov, G. Schanz, M. Steinbrück, J. Stuckert, Z. Hozer, G. Bandini, J.C. Birchley, T. von Berlepsch, I. Kleinhietpass, M. Buck, J.A.F. Benitez, E. Virtanen, S. Marguet, G. Azarian, A. Caillaux, H. Plank, A. Boldyrev, M. Veshchunov, V. Kobzar, Y. Zvonarev, A. Goryachev
Nuclear Engineering and Design 235, 173 (2005)
http://dx.doi.org/10.1016/j.nucengdes.2004.08.050

On the radiolytic decomposition of colloidal silver iodide in aqueous suspension
S. Güntay, R.C. Cripps, B.S. Jäckel, H. Bruchertseifer
Nuclear Technology 150, 303 (2005)

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2004 and before

ARTIST: introduction and first results
S. Güntay, D.J. Suckow, A. Dehbi, R. Kapulla
Nuclear Engineering and Design 231, 109 (2004)
http://dx.doi.org/10.1016/j.nucengdes.2004.02.012

Analysis of iodine species in aqueous solutions
H. Bruchertseifer, R.C. Cripps, S. Güntay, B.S. Jäckel
Analytical and Bioanalytical Chemistry 375, 1107 (2003)
http://dx.doi.org/10.1007/s00216-003-1779-3

Fission product iodine release and retention in nuclear reactor accidents - experimental programme at PSI
H. Bruchertseifer, R.C. Cripps, S. Güntay, B.S. Jäckel
Czechoslovak Journal of Physics 53, 611 (2003)
http://dx.doi.org/10.1007/s10582-003-0079-7

Electrostatic precipitator collection efficiency and trace element emissions from co-combustion of biomass and recovered fuel in fluidized-bed combustion
T.M. Lind, J. Hokkinen, J.K. Jokiniemi, S. Saarikoski, R. Hillamo
Environmental Science & Technology 37, 2842 (2003)
http://dx.doi.org/10.1021/es026314z

Validation of severe accident codes against Phebus FP for plant applications: status of the PHEBEN2 project
A.V. Jones, S. Dickinson, C. de Pascale, N. Hanniet, L.E. Herranz, F. de Rosa, G. Henneges, J. Langhans, C. Housiadas, V. Wichers, J.C. Birchley, S. Paci, F. Martin-Fuentes
Nuclear Engineering and Design 221, 225 (2003)
http://dx.doi.org/10.1016/S0029-5493(02)00340-0

Core loss during a severe accident (COLOSS)
B. Adroguer, P. Chatelard, J.P. van Dorsselaere, C. Duriez, N. Cocuaud, L. Bellenfant, D. Bottomley, V. Vrtilkova, K. Müller, W. Hering, C. Homann, W. Krauss, A. Miassoedov, M. Steinbrück, J. Stuckert, Z. Hozer, G. Bandini, J.C. Birchley, T. von Berlepsch, M. Buck, J.A.F. Benitez, E. Virtanen, S. Marguet, G. Azarian, H. Plank, M. Veshchunov, Y. Zvonarev, A. Goryachev
Nuclear Engineering and Design 221, 55 (2003)
http://dx.doi.org/10.1016/S0029-5493(02)00344-8

Containment behaviour in the event of core melt with gaseous and aerosol releases (CONGA)
E. Friesen, J. Meseth, S. Güntay, D.J. Suckow, J.L. Jimenez, L.E. Herranz, V. Peyres, G.F. De Santi, A. Krasenbrink, M. Valisi, L. Mazzochi
Nuclear Engineering and Design 209, 253 (2001)
http://dx.doi.org/10.1016/S0029-5493(01)00408-3

Aerosol retention in low-subcooling pools under realistic accident conditions
A. Dehbi, D.J. Suckow, S. Güntay
Nuclear Engineering and Design 203, 229 (2001)
http://dx.doi.org/10.1016/S0029-5493(00)00343-5